05000296/LER-2004-003, Regarding Main Steam Relief Valve Inoperability LCO Exceeded During Operating Cycles 10 and 11 Due to Setpoint Drift
| ML070570224 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/15/2007 |
| From: | O'Grady B Tennessee Valley Authority |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| LER 04-003-00 | |
| Download: ML070570224 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 2962004003R00 - NRC Website | |
text
February 15, 2007 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D. C. 20555-0001
Dear Sir:
TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN) -
UNIT 3 - DOCKET 50-296 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-296/2004-003-000 The enclosed report provides details of failure to meet the requirements of the Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.3 concerning main steam relief valve (MSRV) operability associated with the Unit 3 operating cycles 10 and 11.
Similar MSRV performance prior to calendar year 2001 was reported by TVA to NRC via LER. However, TVA did not report the failure to meet TS following the Unit 3 operating cycles 10 and 11 in 2002 and 2004. The failure to report the occurrences have been addressed by the TVA Corrective Action Program. LER 296/2006-01 was submitted for Unit 3 Cycle 12 operation. This LER, 296/2004-003-00, addresses the past conditions (i.e., 2002 and 2004) which had not been previously reported.
As such, in accordance with 10 CFR 50.73(a)(2)(i)(B), TVA is reporting this as any operation or condition prohibited by the units TS. There are no commitments contained in this letter.
Sincerely, Original signed by:
Brian OGrady cc: See page 2
U.S. Nuclear Regulatory Commission Page 2 February 15, 2007 Enclosure cc (Enclosure):
Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Malcolm T. Widmann, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970
U.S. Nuclear Regulatory Commission Page 3 February 15, 2007 WDC:DTL:BAB Enclosure cc (Enclosure):
M. Bajestani, NAB 1A-BFN A. S. Bhatnagar, LP 6A-C R. H. Bryan, BR 4X-C R. G. Jones, POB 2C-BFN G. V. Little, BOB 2C-BFN B. J. O'Grady, PAB 1E-BFN R. A. DeLong, SAB 1E-BFN K. W. Singer, LP 6A-C P. D. Swafford, LP 6A-C E. J. Vigluicci, WT 6A-K NSRB Support, LP 5M-C INPO:LEREvents@inpo.org EDMS WT CA - K S:lic/submit/subs/ler/296 2004 03.doc
NRC FORM 366 (7-2001)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 06/30/2007
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Browns Ferry Unit 3
- 2. DOCKET NUMBER 05000296
- 3. PAGE 1 OF 7
- 4. TITLE Main Steam Relief Valve Inoperability LCO Exceeded During Operating Cycles 10 and 11 due to Setpoint Drift
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME none DOCKET NUMBER N/A 06 17 2004 2004-003-00 02 15 2007 FACILITY NAME none DOCKET NUMBER N/A
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §:(Check all that apply)
- 9. OPERATING MODE 1
20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER
- 10. POWER LEVEL 100 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D) specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) This phenomenon has only a relatively small impact on the MSRV function. BFN has installed compensatory mitigation hardware. BFN is continuing to work with other industry stakeholders toward the total elimination of this issue.
C.
Additional Information
Browns Ferry corrective actions for rework of the valves in Unit 3 Cycles 10 and 11 are documented in BFPER 961764 and PER 61823. The failure to report the MSRV setpoint drift is documented in PER 112190.
D.
Safety System Functional Failure Consideration:
The condition being reported involves only setpoint drift of varying numbers of MSRVs on Unit 3. The safety/relief function provided by these valves was not compromised at any time.
As such, a safety system functional failure did not result from this condition.
E.
Loss of Normal Heat Removal Consideration:
The condition being reported did not involve a reactor scram.
VIII. COMMITMENTS
None.